In cooperation with the Iranian Nuclear Society

Estimation of the frequency of occurrence for grid-related loss of offsite power (GR-LOOP) to a nuclear power plant

Document Type : Research Paper

Authors

1 School of Mechanical Engineering, Shiraz University, P.O.Box: 7193616548, Shiraz – Iran

2 Nuclear Safety and Reactor Research School, Nuclear Science and Technology Research Institute, AEOI, P.O.Box: 11364-3486, Tehran - Iran

Abstract
According to the safety analyses, GR-LOOP holds the most significant contribution in the Core Damage Frequency of Nuclear Power Plants. Since this, in turn, depends on the GR-LOOP frequency of occurrence, an analytical method is presented to identify and evaluate the post-fault GR-LOOP scenarios. The probabilistic module of the hybrid method develops the post-fault sequences regarding the response of the line distance protection to 3-phase short circuit faults. Then, GR-LOOP consequences and frequency are identified by interpretation of the relevant parameters from the transient stability simulations of the post-fault (3Ph-SC) grid behavior. GR-LOOP frequency is estimated as 5.87E-04, 6.25E-04, and 8.60E-04/ (reactor-year) for three NPPs in New England Test System grid as a case study. To this end, 2482 probabilistic sequences and 408 dynamic post-fault scenarios were evaluated for each NPP. The results indicate that GR-LOOP occurrence depends on the real-time values of grid parameters, including the components specifications, pre-fault load flow quantities, and network configuration. Furthermore, the observed difference amongst the GR-LOOP sequences for differently-located NPPs in the grid questions the uncertainty of using mean generic frequencies. Regarding the inapplicability of the existing grid reliability assessment approaches, the hybrid method is recommended as an alternative for GR-LOOP evaluation. Besides, it can reveal the design weaknesses and prioritize the operational tasks via the competitive benefits of employing PSA techniques. Albeit, more precision needs more modifications in both modeling and calculation details, which, in turn, increases the complexity.

Highlights

1.             NUREG/CR-1150. Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants. Washington Dc.: U.S. Nuclear Regulatory Commission (1990).

 

2. NUREG/CR-4550. Analysis of Core Damage Frequency From Internal Events: Methodlogy Guidelines. U.S. Nuclear Regulatory Commission (1987).

 

3. P.L. BNPP, Level 1 PSA on the Project of Reconstruction and Completion of Unit 1 NPP “Bushehr", Revision 3. Atomic Energy Organization of Iran (2003).

 

4. 10CFR52. Early Site Permits; Standard Design Certification; and Combined Licenses for Nuclear Power Plants. Nuclear Regulatory Commission (NRC) (2017).

 

5. A. Volkanovski, et al, Analysis of Loss of Offsite Power Reported in Nuclear Power Plants. 234-248 (2016).

 

6. S. Kamyab, et al, Analysis of Possible Exemption for Passive-Designed-Profited NPPs from GDC 17 of 10CFR50 Case Study: AP1000 versus APWR and EPR, International Reliability and Safety Engineering Conference. Shiraz (2018).

 

7. S. Eide, C. Gentillon, T. Wierman, NUREG/CR-6890, Vol. 1: Reevaluation of Station Blackout Risk at Nuclear Power Plants: Analysis of Loss of Offsite Power Events: 1986-2004. U.S. Nuclear Regulatory Commission (2005).

 

8. NUREG/CR-6928. Industry-Average Performance for Components and Initiating Events at U.S. Commercial Nuclear Power Plants. Idaho National Laboratory (2007).

 

9. A. Annex, Advance Light Water Reactor Utility Requirement Document : Vol II: ALWR Evolutionary Plant. Electrical Power Research Institute (3/1999).

 

10. R. Billinton, R. Allan, Basic Power System Reliability Concepts, 365-384 (1990).

 

11. M. Cepin, Advantages and difficulties with the application of methods of probabilistic safety assessment to the power systems reliability, 136-140 (2012).

 

12. S. Kamyab, et al, Development of a Hybrid Method to Assess the Grid-related LOOP Scenarios for an NPP, Reliability Engineering System Safety (Under Review) (2020).

 

13. A. Volkanovski, M. Cˇepin, B. Mavko, Application of the fault tree analysis for assessment of power system reliability, 94 , 1116–1127 (20009).

 

14. P. Henneaux, P.-E. Labeau, J.C. Maun, A Level-1 Probabilistic Risk Assessment to Blackout Hazard in Transmission Power Systems, 41-52 (2012).

 

15. L. Haarlaa, et al, A method for analysing the reliability of a transmission grid, 277-287 (2008).

 

16. D. Marks, Loss of Offsite Power — Three Unit Trip (LER 2004-006-01). LER (2004).

 

17. PowerFactory2014, DIgSILENT PowerFactory, Version 15. Germany: Siemense (2014).

 

18. RiskSpectrum2016, RiskSpectrum PSA© Software Manual, Version 1.1.2.0. ScandPower (2016).

 

19. NG-T-3.8. Nuclear Energy Series, NG-T-3.8: Electric Grid Reliability and Interface with Nuclear Power Plants. Vienna: Internation Atomic Energy Agency. IAEA (2012).

 

20. Iran Electricity Transmission Network Relay and Protection System Regulations, Second Edition, Iran Electricity Network Management Company (1396) IGMC.

Keywords


1.             NUREG/CR-1150. Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants. Washington Dc.: U.S. Nuclear Regulatory Commission (1990).
 
2. NUREG/CR-4550. Analysis of Core Damage Frequency From Internal Events: Methodlogy Guidelines. U.S. Nuclear Regulatory Commission (1987).
 
3. P.L. BNPP, Level 1 PSA on the Project of Reconstruction and Completion of Unit 1 NPP “Bushehr", Revision 3. Atomic Energy Organization of Iran (2003).
 
4. 10CFR52. Early Site Permits; Standard Design Certification; and Combined Licenses for Nuclear Power Plants. Nuclear Regulatory Commission (NRC) (2017).
 
5. A. Volkanovski, et al, Analysis of Loss of Offsite Power Reported in Nuclear Power Plants. 234-248 (2016).
 
6. S. Kamyab, et al, Analysis of Possible Exemption for Passive-Designed-Profited NPPs from GDC 17 of 10CFR50 Case Study: AP1000 versus APWR and EPR, International Reliability and Safety Engineering Conference. Shiraz (2018).
 
7. S. Eide, C. Gentillon, T. Wierman, NUREG/CR-6890, Vol. 1: Reevaluation of Station Blackout Risk at Nuclear Power Plants: Analysis of Loss of Offsite Power Events: 1986-2004. U.S. Nuclear Regulatory Commission (2005).
 
8. NUREG/CR-6928. Industry-Average Performance for Components and Initiating Events at U.S. Commercial Nuclear Power Plants. Idaho National Laboratory (2007).
 
9. A. Annex, Advance Light Water Reactor Utility Requirement Document : Vol II: ALWR Evolutionary Plant. Electrical Power Research Institute (3/1999).
 
10. R. Billinton, R. Allan, Basic Power System Reliability Concepts, 365-384 (1990).
 
11. M. Cepin, Advantages and difficulties with the application of methods of probabilistic safety assessment to the power systems reliability, 136-140 (2012).
 
12. S. Kamyab, et al, Development of a Hybrid Method to Assess the Grid-related LOOP Scenarios for an NPP, Reliability Engineering System Safety (Under Review) (2020).
 
13. A. Volkanovski, M. Cˇepin, B. Mavko, Application of the fault tree analysis for assessment of power system reliability, 94 , 1116–1127 (20009).
 
14. P. Henneaux, P.-E. Labeau, J.C. Maun, A Level-1 Probabilistic Risk Assessment to Blackout Hazard in Transmission Power Systems, 41-52 (2012).
 
15. L. Haarlaa, et al, A method for analysing the reliability of a transmission grid, 277-287 (2008).
 
16. D. Marks, Loss of Offsite Power — Three Unit Trip (LER 2004-006-01). LER (2004).
 
17. PowerFactory2014, DIgSILENT PowerFactory, Version 15. Germany: Siemense (2014).
 
18. RiskSpectrum2016, RiskSpectrum PSA© Software Manual, Version 1.1.2.0. ScandPower (2016).
 
19. NG-T-3.8. Nuclear Energy Series, NG-T-3.8: Electric Grid Reliability and Interface with Nuclear Power Plants. Vienna: Internation Atomic Energy Agency. IAEA (2012).
 
20. Iran Electricity Transmission Network Relay and Protection System Regulations, Second Edition, Iran Electricity Network Management Company (1396) IGMC.